FR1249178A - Nuclear reactor core moderator composition for obtaining a flattened flow - Google Patents

Nuclear reactor core moderator composition for obtaining a flattened flow

Info

Publication number
FR1249178A
FR1249178A FR819602A FR819602A FR1249178A FR 1249178 A FR1249178 A FR 1249178A FR 819602 A FR819602 A FR 819602A FR 819602 A FR819602 A FR 819602A FR 1249178 A FR1249178 A FR 1249178A
Authority
FR
France
Prior art keywords
obtaining
nuclear reactor
reactor core
flattened flow
core moderator
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
FR819602A
Other languages
French (fr)
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Application granted granted Critical
Publication of FR1249178A publication Critical patent/FR1249178A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/005—Flux flattening
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Particle Accelerators (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
FR819602A 1959-03-10 1960-02-25 Nuclear reactor core moderator composition for obtaining a flattened flow Expired FR1249178A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US798521A US3081247A (en) 1959-03-10 1959-03-10 Moderator elements for uniform power nuclear reactor

Publications (1)

Publication Number Publication Date
FR1249178A true FR1249178A (en) 1960-12-23

Family

ID=25173611

Family Applications (1)

Application Number Title Priority Date Filing Date
FR819602A Expired FR1249178A (en) 1959-03-10 1960-02-25 Nuclear reactor core moderator composition for obtaining a flattened flow

Country Status (4)

Country Link
US (1) US3081247A (en)
BE (1) BE588349A (en)
FR (1) FR1249178A (en)
GB (1) GB919287A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3175955A (en) * 1961-01-11 1965-03-30 Richard D Cheverton Gradient fuel plates

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3186913A (en) * 1960-05-18 1965-06-01 North American Aviation Inc Graphite moderated nuclear reactor
GB1384617A (en) * 1972-06-30 1975-02-19 British Nuclear Design Constr Integral-fuel blocks
US4148687A (en) * 1976-08-26 1979-04-10 Institute Of Nuclear Energy Research Method for savings in nuclear reactors by using beryllium rods in fuel bundles
US4235669A (en) * 1978-03-30 1980-11-25 The United States Of America As Represented By The United States Department Of Energy Nuclear reactor composite fuel assembly
US4569820A (en) * 1981-05-13 1986-02-11 Ga Technologies Inc. Nuclear reactor core and fuel element therefor
CN111801742A (en) * 2018-01-22 2020-10-20 奥卓安全核能公司 Composite moderator for nuclear reactor system
KR102561185B1 (en) * 2018-01-22 2023-07-27 울트라 세이프 뉴클리어 코포레이션 Composite moderators for nuclear reactor systems
CN110706829B (en) * 2019-10-18 2021-05-07 中国科学院合肥物质科学研究院 Integrated compact reactor core with radial power flattening function
US11830630B2 (en) * 2020-10-26 2023-11-28 Westinghouse Electric Company Llc Enhanced graphite neutron reflector with beryllium oxide inclusions

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2774730A (en) * 1944-09-05 1956-12-18 Gale J Young Neutronic reactor having a flattened activity curve
US2890158A (en) * 1944-12-19 1959-06-09 Leo A Ohlinger Neutronic reactor
US2810689A (en) * 1945-11-06 1957-10-22 Eugene P Wigner Fluid moderated reactor
US2852456A (en) * 1953-11-17 1958-09-16 Elmer J Wade Neutronic reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3175955A (en) * 1961-01-11 1965-03-30 Richard D Cheverton Gradient fuel plates

Also Published As

Publication number Publication date
BE588349A (en)
GB919287A (en) 1963-02-20
US3081247A (en) 1963-03-12

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